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AbstractAbstract
[en] Data and information collection aimed in order to meet the needs of the initial design for pilot plant of monazite processing into thorium oxide (ThO_2). The content of thorium in monazite is high in Indonesia between 2.9 to 4.1% and relatively abundant in Bangka Belitung Islands. Thorium can be used as fuel because of its potential is more abundant instead of uranium. Plant of thorium oxide commercially from monazite established starting from pilot uranium. Plant of thorium oxide commercially from monazite established starting from pilot plant in order to test laboratory data. Pilot plant design started from initial design, basic design, detailed design, procurement and construction. Preliminary design needs includes data feed and products, a block diagram of the process, a description of the process, the determination of process conditions and type of major appliance has been conducted. (author)
Original Title
Kebutuhan desain awal pada pilot plant pengolahan Monazit menjadi Thorium Oksida (ThO_2)
Primary Subject
Source
Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 10 refs., 5 tabs., 1 fig.
Record Type
Journal Article
Journal
Eksplorium; ISSN 0854-1418; ; v. 35(2); p. 131-141
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Abdul Jami; Marliyadi Pancoko
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2013
AbstractAbstract
[en] The design of HF gas absorber through the design steps of determination of equilibrium curve, the solvent nominal and number stages to be used and calculation of absorber dimension. Absorption process uses deminerazed water as solvent and the results of calculation as follows: the minimum solvent needed as much as 3887,2015 kg/hour and for normal operating use the solvent as much as 11661 kg/hour; number of stages are 4; coloum diameter is 1,1 m and total coloum high is 11,2 m; shell thickness is 3/16 inch; material construction is SS-316 L; and raschig ring of ceramic is selected to be used as packing material. (author)
Original Title
Perekayasaan menara penyerap gas HF pada proses konversi UF6 menjadi UO2 melalui jalur ammonium uranil karbonat (AUK)
Primary Subject
Secondary Subject
Source
Wiranto Budi Santoso; Bambang Galung Susanto; Ari Satmoko (Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 419 p; ISSN 1693-3346; ; Nov 2013; p. 47-65; Scientific Meeting of Nuclear Devices Engineering; Pertemuan Ilmiah Perekayasaan Perangkat Nuklir; Serpong (Indonesia); 14 Nov 2013; Also available from Center for Utilization of Informatics and Region Strategic Nuclear, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 8 refs.; 1 tabs.; 6 figs.
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AbstractAbstract
[en] Researches conducted by Batan's researchers have resulted in a number competences that can be used to produce goods and services, which will be applied to industrial sector. However, there are difficulties how to convey and utilize the R and D products into industrial sector. Evaluation results show that each research result should be completed with techno-economy analysis to obtain the feasibility of a product for industry. Further analysis on multy-product concept, in which one business can produce many main products, will be done. For this purpose, a software package simulating techno-economy I economic feasibility which uses deterministic and stochastic data (Monte Carlo method) was been carried out for multi-product including side product. The programming language used in Visual Basic Studio Net 2003 and SQL as data base processing software. This software applied sensitivity test to identify which investment criteria is sensitive for the prospective businesses. Performance test (trial test) has been conducted and the results are in line with the design requirement, such as investment feasibility and sensitivity displayed deterministically and stochastically. These result can be interpreted very well to support business decision. Validation has been performed using Microsoft Excel (for single product). The result of the trial test and validation show that this package is suitable for demands and is ready for use. (author)
Original Title
Simulasi teknoekonomi berbasis data deterministik dan stokastik untuk produk rekayasa hasil litbang BATAN
Primary Subject
Secondary Subject
Source
Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 5 refs.; 3 figs.
Record Type
Journal Article
Journal
Prima (Tangerang); ISSN 1411-0296; ; v. VII(13); p. 451-456
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Abdul Jami; Hafni Lissa Nuri, E-mail: Abduljami2011@gmail.com2013
AbstractAbstract
[en] Mixer settler is technically designed for extraction and separation process of uranium from phosphoric acid solution. Design calculation results shows that: the mixer settler consists of two parts: part of extraction process in the mixer tank and part of separation process in settler tank. The mixer tank type of box with 4 baffles, the size of mixer tank, 0.8 m width, 0.8 m length, 1 m high of liquid, 1.05 m high of mixer tank, stirrer type of disk 6 blade, and power of mixing 4 hp and the settler tank type of rectangular with size of settler tank, 0.8 m width 5 m length, 1 m high of liquid, 1.05 m high of settler tank. For uranium recovery efficiency up to 91%, extraction process is done in 3 stage counter current flow using a solvent Organic (O) DEHPA-TOPO in Kerosene at a phase of ratio A/O of 2:1. The aqueous enter through stage 3 and the organic solvent enter through stage 1. The process of settling occurred with the value of settling velocity is 0.000694 m/s, dispersion factor Ψ = 0.3638 and the light fraction as the dispersed phase and value of Reynolds number (NRE) = 3,438. Because of the Reynolds number is lower than 5,000, it indicates that the quality of the separation is very good. (author)
Original Title
Perekayasa mixer settler untuk ekstraksi siklus II pada recovery uranium dalam larutan asam fosfat
Primary Subject
Source
Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 8 refs., 3 tabs., 4 figs.
Record Type
Journal Article
Journal
Eksplorium; ISSN 0854-1418; ; v. 34(1); p. 23-34
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AbstractAbstract
[en] Pilot plant of ThO2 from tailing monazite processing with capacity of 100 kg/day is a process for recovering thorium ThO2 that consists of 3 process stages: preparation process, extraction process and thermal decomposition process. One of equipment's required for support in third process is basket centrifuge for filtration process of thorium hydroxide. In order to design the basket centrifuge engineering calculations are performed. The type of the basket centrifuge is vertical drum with volume basket is 0.23 m3. The dimension is 1.2 m in diameter 0.20 m in height. Maximum load is 1,800 kg, construction material is SS-316L, time of filtration is 96 second and total power required is 11 kW. (author)
Original Title
Desain basket sentrifugal untuk proses filtrasi slurry torium hidroksida
Primary Subject
Source
Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 5 refs.; 5 tabs.; 3 figs.
Record Type
Journal Article
Journal
Prima (Tangerang); ISSN 1411-0296; ; v. 13(1); p. 9-17
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHALCOGENIDES, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CONCENTRATORS, CORROSION RESISTANT ALLOYS, DECOMPOSITION, DISPERSIONS, FUNCTIONAL MODELS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, HYDROGEN COMPOUNDS, HYDROXIDES, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS, MINERALS, MIXTURES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, OXIDES, OXYGEN COMPOUNDS, PHOSPHATE MINERALS, RADIOACTIVE MATERIALS, RADIOACTIVE MINERALS, SEPARATION PROCESSES, STAINLESS STEELS, STEEL-CR17NI12MO3-L, STEELS, SUSPENSIONS, THERMOCHEMICAL PROCESSES, THORIUM COMPOUNDS, THORIUM MINERALS, TRANSITION ELEMENT ALLOYS
LanguageLanguage
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Marliyadi Pancoko; Abdul Jami
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2011
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2011
AbstractAbstract
[en] Mixer-settler plays important roles in uranium recovery process from phosphoric acid. To flow phosphoric acid from feeder tank to mixer settler, constant fluid flow rate is needed. Therefore, this program selects a pump with positive displacement of reciprocating type having specification of plunger single acting 5 x4 triplex, and power 2 HP, to flow phosphoric acid solution with flow rate of 20 kg/s (242 gpm), density of 1300 kg/m3, and viscosity of 4.5 cPo and suction static head of 2 m and discharge static head of 6.4 m. From cavitation evaluation. NPSH available of 8.9 m which waS greater than NPSH required of 4.5 m (specification from pump maker) was obtained. (author)
Original Title
Kriteria pemilihan pompa untuk mengalirkan larutan asam fosfat ke mixer settler pada proses recovery uranium dari asam fosfat
Primary Subject
Source
Achmad Suntoro; Wiranto Budi Santoso; Bambang Galung Susanto; Sri Mulyono Atmojo; Ari Satmoko (Badan Tenaga Nuklir Nasional (BATAN), Jakarta (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 378 p; ISSN 1693-3346; ; 30 Nov 2011; p. 167-174; Scientific Engineering Meeting for Nuclear Devices; Pertemuan Ilmiah Rekayasa Perangkat Nuklir; Serpong (Indonesia); 30 Nov 2011; Also available from Directorate of Repository, Multimedia and Scientific Publishing, National Research and Innovation Agency, Kawasan Sains dan Teknologi - BRIN, KST B. J. Habibie, Gedung 120 TMC, Jl. Raya Puspiptek Serpong, Phone (+62 21) 7560009, Tangerang Selatan 15314 (ID); 9 refs.; 1 tab.; 6 figs.
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AbstractAbstract
[en] Pilot plant of ThO2 from tailing monazite processing with capacity of 100 kg/day is a process for recovering thorium ThO2 that consists of 3 process stages: preparation process, extraction process and thermal decomposition process. One of equipments required in the thermal decomposition is electric furnace. In order to design the electric heating furnace engineering calculations are performed. The type of the electric furnace is rectangular with volume chamber is 0,3 m3. The dimension is 0,9 m in depth, 0,6 m in width and 0,6 m in height. Construction material is SS-316L, isolator from firebrick is 3 inch and of thickness total power required is 20 kW. (author)
Original Title
Desain electric furnace untuk proses dekomposisi thermal thorium oxalate hexahydrate
Primary Subject
Source
Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 5 refs.; 3 tabs.; 3 figs.
Record Type
Journal Article
Journal
Prima (Tangerang); ISSN 1411-0296; ; v. 12(2); p. 19-28
Country of publication
ACTINIDE COMPOUNDS, ACTINIDES, CARBOXYLIC ACID SALTS, CHALCOGENIDES, CHEMICAL REACTIONS, DECOMPOSITION, DIMENSIONS, ELEMENTS, FUNCTIONAL MODELS, FURNACES, HEATING, MATERIALS, METALS, MINERALS, OXIDES, OXYGEN COMPOUNDS, PHOSPHATE MINERALS, RADIOACTIVE MATERIALS, RADIOACTIVE MINERALS, SEPARATION PROCESSES, SOLID WASTES, THERMOCHEMICAL PROCESSES, THORIUM COMPOUNDS, THORIUM MINERALS, WASTES
LanguageLanguage
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Abdul Jami; Hafni Lissa Nuri
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2011
Proceedings of the Scientific Engineering Meeting for Nuclear Devices2011
AbstractAbstract
[en] A settling tank has been designed for AUC (Ammonium Uranyl Carbonate) separation process from liquid containing of NH4F. From design calculation results are concluded that: the settling tank type is continuous clarifier of vertical cylindris with size of diameter 0.40 m, hight of fluid 3.18 m, hight of tank 3.5 m. Because the diameter of tank 0.40 m is lower than its critical diameter (0.427 m) for slurry of AUC, the design of tank is safe geometrically. The settling velocity is 0.0008824 m/s. above the rate of linear overflow that is 0.0004665 m/s, theoretically there is no solid particles carried away by the stream overflow and the separation process goes well. (author)
Original Title
Perekayasaan tangki pengenap untuk memisahkan (NH4)4UO2(CO3)3 dari cairan NH4F
Primary Subject
Secondary Subject
Source
Achmad Suntoro; Wiranto Budi Santoso; Bambang Galung Susanto; Sri Mulyono Atmojo; Ari Satmoko (Badan Tenaga Nuklir Nasional (BATAN), Jakarta (Indonesia)) (eds.); Center for Nuclear Device Engineering, National Nuclear Energy Agency, Serpong (Indonesia); 378 p; ISSN 1693-3346; ; 30 Nov 2011; p. 194-201; Scientific Engineering Meeting for Nuclear Devices; Pertemuan Ilmiah Rekayasa Perangkat Nuklir; Serpong (Indonesia); 30 Nov 2011; Also available from Directorate of Repository, Multimedia and Scientific Publishing, National Research and Innovation Agency, Kawasan Sains dan Teknologi - BRIN, KST B. J. Habibie, Gedung 120 TMC, Jl. Raya Puspiptek Serpong, Phone (+62 21) 7560009, Tangerang Selatan 15314 (ID); 6 refs.; 4 tabs.; 3 figs.
Record Type
Miscellaneous
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Conference
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Abdul Jami; Hafni Lissa Nuri; Hana Subhiyah, E-mail: abduljami@batan.go.id2021
AbstractAbstract
[en] Scintillation plastic made of polystyrene is one components of the radiation portal monitor as a detector. The basic principle of this scintillation plastic detector is to convert radiation energy into ultraviolet light and into visible light in the form of a purple light in the wavelength range of 400 ∼500 nm, which is then converted into an electrical signal by a photomultiplier tube. Studies on instrument technology for the analysis of scintillated plastics as detectors have been carried out on UV-Vis Spectrophotometer, Atomic Emission Spectrophotometer, and Photo Multiplier Tube (PMT). UV-Vis Spectrophotometer and Atomic Emission Spectrophotometer use an ultraviolet light source or visible light, so that only the secondary dopant works, whereas the primary dopant does not work. Meanwhile, the photomultiplier tube is used to test the ability of scintillated plastics to detect gamma rays based on the electrical signal generated. The electrical signal generated indicates that the primary and secondary dopants are functioning properly because they are able to convert gamma radiation into visible light waves. So the Photo Multiplier Tube is used to analyze the ability of scintillated plastics to detect gamma ray radiation, and to measure the wavelength of the scintillated plastic scintillation light using UV-Vis Spectrophotometer or Atomic Emission Spectrophotometer. (author)
Original Title
Kajian teknologi instrumen untuk analisis plastik sintilasi berbasis polistirena
Primary Subject
Source
11refs.; 8 figs
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Journal Article
Journal
Prima (Tangerang); ISSN 1411-0296; ; v. 18(2); p. 1-7
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Abdul Jami; Budi Santoso, E-mail: abduljami@batan.go.id2019
AbstractAbstract
[en] The primary cooling system for TRIGA plate reactors uses natural convection and forced convection systems. Further more, this cooling system must be equipped with a convection valve. Natural convection occurs when the reactor goes out, the convection valve opens and forced convection occurs when the reactor operates, the convection valve is closed. The development and modification of the existing cooling system has been carried out as a plate TRIGA reactor primary cooling system. Modifications are made by adding equipment decay tanks, pipe fittings, valves, control instruments, and changing connecting pipe lines between equipment. Modification results in the form of process flow diagram (PFD), Piping & Instrumentation Diagram (P & ID), layout, plot plan, and isometric. The difference in the height of the heat exchanger and the location of the reactor can cause back flow, so the anti siphon valve needs to be installed on this connecting pipe. The changes in the pipeline track between the pump and reactor, the reactor exit pipe through the hole of beam port into the decay tank and then towards the primary pump. In the layout drawing, the decay tank is equipped with a level indicator and vent, with the aim of ensuring that the decay tank is full of water and no gas or steam is trapped, because it can cause cavitation on the pump. (author)
Original Title
Desain sistem pendingin primer reaktor TRIGA pelat
Primary Subject
Secondary Subject
Source
Available from Center for Informatics and Nuclear Strategic Zone Utilization, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560895, Serpong, Tangerang Selatan 15314 (ID); 8 refs.; 6 figs.
Record Type
Journal Article
Journal
Prima (Tangerang); ISSN 1411-0296; ; v. 16(1); p. 34-42
Country of publication
CONTAINERS, CONVECTION, COOLING SYSTEMS, ENERGY SYSTEMS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EQUIPMENT, HEAT TRANSFER, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, MASS TRANSFER, MEASURING INSTRUMENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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